ML20082T137
| ML20082T137 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/05/1983 |
| From: | Wells D DETROIT EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 105, 10CFR-050.55E, 10CFR-50.55E, DER-831205-01, DER-831205-1, EF2-66482, NUDOCS 8312150173 | |
| Download: ML20082T137 (2) | |
Text
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.7 Donald A. Wells Manager.ouahty Ascurance -
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4313) 237-9657
- 2000 Secor.d Avenue 31 3
December 5, 1983 EF2-66482 Mr. James'G. Keppler, Regional Administrator Region.III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen-Ellyn, Illinois 60137
Subject:
Report ' of 10CFR50.55(e) Item on Thermal Separation Criteria Violations (#105)
Dear Mr. Keppler:
- On November:4, 1983, Detroit Edison's Mr. J.E. Durkin, Quality
. Engineer - Construction Quality Ascurance, telephoned Mr. P. Pelke of
- NRC Region III to report on Thermal Separation Criteria violations in
. the drywell at the Fermi' 2 site.
A number of instances exist where thermal separation between electrical cables and hot pipes or equipment is.less than specified. This could
~ cause'a premature. failure of' electrical cables.-
The Engineering Research Department did studies on heat transfer from steam pipes'to electrical conduits and trays. Various curves were developed between pipe distance / diameter ratios vs pipe skin tempera-
- ture and temperature rise.- Tables were developed from these curves.
Design Calculation 2119 " Calculation of Separation Distance to be Maintained Between Electrical Conduits, Trays and Steam Lines (Mechanical Hot Pipes)" was issued listing the ' curves and the tables.
Separation distance between electrical conduits or trays and steam pipes can.be calculated from the tables in DC 2119.
Edison Field Endineering has issued a design change revising the
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electrical specification for inspection purposes in the drywell. This
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design change is based on DC 2119. Currently, a walkdown is being performed in the drywell per the design change. Any violations will be evaluated by 'the Engineering Research Department and the Generation Engineering Department on 'a case-by-case basis and disposed accordingly.
l If any distance between steam pipes and electrical conduits or trays is found to be unacceptable, modifications will be made to correct any problems.
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\\h 8312150173 831205 PDR ADOCK 050003p 81983 l DEC t
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Mr. James'G. Keppler,' Regional Administrator
'- December 5, 1983 EF2-66482
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Page'2 Another report on'this item,.either. interim or final, will be sent i
when'further'information is available. If you have questions concern-
- ing this matter, please contact'Mr. G.M..Trahey,: Assistant Director -
Project.; Quality Assurance.
.Very..truly-yours, r
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Y)]
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DAW /EHN/cp cc:
Mr. Richard DeYoung, Director-Office of Inspection and Enforcement
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LU;S. Nuclear-Regulatory Commission Washington,LD.C.= 20555
- Mr. Paul Byron, Senior Resident Inspector U.S. Nuclear Regulatory Commission
.6450 North Dixie Highway-Newport,' Michigan 48166 V
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